| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/04/2017 - 08/07/2017 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52875 | Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: INTERNATIONAL PAPER
Region: 1
City: GEORGETOWN State: SC
County:
License #: 060
Agreement: Y
Docket:
NRC Notified By: ANDREW ROXBURGH
HQ OPS Officer: STEVEN VITTO | Notification Date: 07/28/2017
Notification Time: 09:51 [ET]
Event Date: 07/27/2017
Event Time: [EDT]
Last Update Date: 07/28/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAN SCHROEDER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE SHUTTER STUCK IN CLOSED POSITION
The licensee, International Paper, provided notification to the South Carolina Department of Health and Environmental Control of a stuck shutter on a Berthold Model LB7440 fixed gauging device. The shutter is stuck in the closed position. Corrosion was found on the shutter roll pin causing the shutter mechanism to fail. The gauging device contains 10 mCi of Cs-137. A measurement of 20 mR/hr was detected in front of the gauge. The licensee has removed the gauge from service and is awaiting a shipping container to return the gauge to the manufacturer.
SC license # 060. |
| Agreement State | Event Number: 52878 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: MAYO CLINIC
Region: 1
City: JACKSONVILLE State: FL
County:
License #: 1812-3
Agreement: Y
Docket:
NRC Notified By: TIM DUNN
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/28/2017
Notification Time: 16:00 [ET]
Event Date: 07/28/2017
Event Time: [EDT]
Last Update Date: 07/28/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAN SCHROEDER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - DOSE RECEIVED EXCEEDED PRESCRIBED DOSE
The following information was received from the State of Florida via email:
"[The State of Florida] received a call from the [Mayo Clinic] RSO [Radiation Safety Officer] to report a medical event that occurred at Mayo clinic. While performing a 90cc volume liver ablation, a female patient was to receive a 340 Gy dose, but it was later discovered that the dose delivered was 800 Gy. The physician has been notified, and is contacting the patient to inform her of the overdose and verify that there are no unusual side effects. A written report from the RSO will be sent to this office before Aug. 11th detailing the cause of the incident and corrective actions to be taken.
"Incident Number: FL17-230"
The isotope involved is Y-90 [Yttrium-90] Spheres.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Power Reactor | Event Number: 52888 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: WILLIAM ROBERTS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/04/2017
Notification Time: 17:25 [ET]
Event Date: 08/04/2017
Event Time: 15:11 [EDT]
Last Update Date: 08/04/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text SECONDARY CONTAINMENT INOPERABLE DUE TO OPENING IN SERVICE WATER PIPING
"On August 4, 2017, at 1511 EDT, Unit 1 Secondary Containment was declared inoperable due to a small (i.e., approximately 0.75 inch diameter) hole in Service Water system piping which was found during ultrasonic testing activities. The affected portion of piping penetrates Secondary Containment and flow in the piping creates a vacuum condition; thus bypassing Secondary Containment. The identified hole is being evaluated with respect to its impact on operability of the Service Water system.
"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(v)(C), as an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material.
"This event did not result in any adverse impact to the health and safety of the public.
"Initial Safety Significance Evaluation: The initial safety significance of this event is minimal. At the time of discovery, Unit 1 was at 100% steady state conditions. Reactor Building Ventilation was in service in a normal alignment. No abnormal radioactivity conditions existed within Secondary Containment.
"Corrective Actions: Temporary repair of the affected Unit 1 Service Water piping has been completed. This repair was evaluated by Engineering and it has been determined that the repair meets the requirements to maintain Secondary Containment operable. Unit 1 Secondary Containment operability was restored at 1704 EDT on August 4, 2017."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 52889 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL CRAWFORD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/06/2017
Notification Time: 00:26 [ET]
Event Date: 08/05/2017
Event Time: 22:35 [EDT]
Last Update Date: 08/06/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JON LILLIENDAHL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 84 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DURING TESTING
"At 2235 [EDT] Nine Mile Point Unit 2 experienced an automatic scram on high reactor pressure. Turbine stop valve testing was in progress at the time of the scram. All control rods inserted. Pressure control is via the turbine bypass valves. The cause of the scram is being investigated.
"This is a 4-Hour report for 10CFR50.72(b)(2)(iv)(B) RPS [Reactor Protection System] Actuation.
"The NRC Resident Inspector has been notified."
Reactor water level is being maintained with normal feedwater flow. No safety or relief valves lifted. The plant is in its normal shutdown electrical lineup. | |